Results 91 to 100 of about 311,592 (233)

First SOLPS-ITER modelling of an X-point radiator in ITER

Nuclear Fusion
For the first time, an X -point radiating (XPR) regime using neon (Ne) seed impurity has been obtained in ITER modelling with the SOLPS-ITER code, including fluid drifts.
A. Poletaeva, V. Rozhansky, E. Kaveeva, V. Korzueva, I. Senichenkov, I. Veselova, R.A. Pitts, X. Bonnin   +7 more
doaj   +1 more source

Review on ASDEX Upgrade operation with tungsten plasma facing components

Nuclear Materials and Energy
With the decision of ITER to start its operation with tungsten as plasma facing material also for the main chamber plasma facing components, the interest in the consequences of the use of W was strongly increased. Although many investigations had already
R. Neu, C. Angioni, V. Bobkov, R. Dux, J. Hobirk, A. Kallenbach, K. Krieger, T. Pütterich, V. Rohde, K. Schmid   +9 more
doaj   +1 more source

Characterization of 3-strap antennas in ASDEX Upgrade

EPJ Web of Conferences, 2017
The response of the local RF current measured at limiters of 3-strap ICRF antenna to variations of power balance and phasing at fICRF=30MHz agrees qualitatively well with EM calculations by TOPICA and RAPLICASOL codes. Measurements of tungsten sputtering
Bobkov Volodymyr, Bilato Roberto, Colas Laurent, Dux Ralph, Faudot Eric, Faugel Helmut, Fünfgelder Helmut, Herrmann Albrecht, Jacquot Jonathan, Kallenbach Arne, Milanesio Daniele, Maggiora Riccardo, Neu Rudolf, Noterdaeme Jean-Marie, Ochoukov Roman, Pütterich Thomas, Tierens Wouter, Zhang Wei   +17 more
doaj   +1 more source

A practical protocol to emulate a reactor scenario on present machines, with application to the ASDEX Upgrade tokamak via predictive modeling

Nuclear Fusion, 2023
In this work, a novel practical strategy to emulate a reactor scenario on present tokamak experiments is presented. A recipe how to scale several relevant parameters from a hypothetical reactor scenario down to present devices is discussed.
E. Fable, P. David, O. Kudlacek, C. Hopf, B. Sieglin, J. Stober, W. Treutterer, M. Weiland, C. Wu, H. Zohm, the ASDEX Upgrade Team   +10 more
doaj   +1 more source

Erosion of tungsten and carbon markers in the outer divertor of ASDEX-Upgrade

, 2007
The erosion of tungsten and carbon marker layers was studied in the outer divertor of ASDEX Upgrade. The outer strike point area and a large fraction of the outer baffle are net erosion areas for both materials. The net erosion rate of carbon is about 10–
Likonen, J., Rohde, V., V Rohde, J L Chen, Mayer, M., Ramos, G., Chen, J.L., J Likonen, ASDEX Upgrade Team, G Ramos, Vainonen-Ahlgren, E., Vainonen-Ahlgren, Elizaveta, Chen, J., Likonen, Jari; id_orcid, E Vainonen-Ahlgren, M Mayer   +15 more
core   +2 more sources

The ASDEX Upgrade UTDC and DIO cards - A family of PCI/cPCI devices for real-time DAQ under Solaris [PDF]

, 2005
A Universal Time to Digital Converter (UTDC) and a Digital I/O (DIO) card have been built to purpose for the new ASDEX Upgrade control system, the Thomson Scattering diagnostic, a renovation of the Magnetic Measurement, and a couple of other diagnostics ...
Lohs, A., G. Raupp, Behler, K. ; https://orcid.org/, K. Lüddecke, Behler, K., Raupp, G., A. Lohs, K. Behler, Lüddecke, K., ASDEX Upgrade Team   +9 more
core   +1 more source

Chemically assisted physical sputtering of Tungsten: Identification via the 6Π→6Σ+ transition of WD in TEXTOR and ASDEX Upgrade plasmas

Nuclear Materials and Energy, 2019
Tungsten (W) is a preferred plasma-facing material for areas of high particle and power impact in present day and future fusion devices. The lifetime of W plasma-facing components (PFCs) under steady-state conditions is limited by erosion processes ...
S. Brezinsek, A. Pospieszczyk, G. Sergienko, R. Dux, M. Cavedon, M. Faitsch, K. Krieger   +6 more
doaj   +1 more source

Fast-ion pressure dominating the mass dependence of the core heat transport in ASDEX Upgrade H-modes

, 2021
H-mode plasmas in ASDEX Upgrade (AUG) using different hydrogen isotopes are analysed with respect to their core transport properties. The experimental results are discussed and we present gyrokinetic simulations which are able to reproduce the ...
P. Schneider, N. Bonanomi, C. Angioni, M. Weiland, M. Cavedon, P. David, R. Fischer, P. Hennequin, J. Hobirk, A. Kappatou, B. Kurzan, R. McDermott, U. Plank, T. Pütterich, F. Ryter, M. Willensdorfer, the ASDEX Upgrade team, and the EUROfusion MST1 Team   +17 more
semanticscholar   +1 more source

Fast-ion D-alpha measurements at ASDEX Upgrade [PDF]

, 2011
A fast-ion D-alpha (FIDA) diagnostic has been developed for the fully tungsten coated ASDEX Upgrade (AUG) tokamak using 25 toroidally viewing lines of sight and featuring a temporal resolution of 10 ms.
R Fischer, McDermott, R., Heidbrink, W., Dux, R., Tardini, G, R Dux, G Tardini, V Igochine, Tardini, G., Fischer, R, Team, the ASDEX Upgrade, B Geiger, Geiger, B, Fischer, R., Geiger, B., Dux, R, Garcia-Munoz, M, McDermott, RM, Heidbrink, W. W., Garcia-Munoz, M., Igochine, V., W W Heidbrink, McDermott, R. M., Igochine, V, ASDEX Upgrade Team, Heidbrink, WW, null null, R M McDermott, M Garcia-Munoz   +28 more
core   +1 more source

The quasi-continuous exhaust regime in JET

Nuclear Fusion
The quasi-continuous exhaust (QCE) regime is a regime that is naturally type-I ELM-free. It combines the high density at the plasma edge needed for power exhaust with the high normalised energy confinement typical for H-mode operation.
M. Faitsch, M. Dunne, E. Lerche, P. Lomas, I. Balboa, P. Bilkova, P. Bohm, A. Kappatou, D. Kos, B. Labit, S. Menmuir, O. Sauter, S. Silburn, E.R. Solano, H.J. Sun, A. Tookey, E. Viezzer, U. Stroth, JET Contributors, the EUROfusion Tokamak Exploitation Team   +19 more
doaj   +1 more source